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Perspectives on Performance Assessment and High-Level Waste Glass in a Geologic Repository

Published online by Cambridge University Press:  25 February 2011

B.P. Mcgrail  and
D.W. Engel
B.P. Mcgrail
Affiliation:
Pacific Northwest Laboratorya), P. O. Box 999, Richland, WA 99352
D.W. Engel
Affiliation:
Pacific Northwest Laboratorya), P. O. Box 999, Richland, WA 99352
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Abstract

The design and analysis of waste package and engineered systems for geologic disposal of radioactive wastes are being conducted in most countries with so-called performance assessment models and associated computer codes that solve the governing equations. The models range in complexity from simple 1-D analytical solutions to multidimensional, multicomponent reactive transport models implemented in large computer codes. Borosilicate waste glass is certainly the most studied and probably best understood waste form that has been developed for encapsulating high-level waste. Reasonably good models are available that describe the reaction kinetics and transformation of the glass into a paragenetic sequence of more stable secondary phases. Given the broad range of computational tools and extensive database on glass/water reactions that is available, it is surprising that little progress has been made to link these models and data in a comprehensive performance assessment of waste glass in a repository setting. In this paper, we will explore reasons why this linkage has not been developed, give several examples illustrating the importance of doing so, and illustrate an approach to accomplish such a linkage.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 333: Symposium V – Scientific Basis for Nuclear Waste Management XVII , 1993 , 99
Copyright
Copyright © Materials Research Society 1994

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References

REFERENCES

1 Strachan, D.M., Bourcier, W.L., and McGrail, B.P.. “Toward a Consistent Model for Glass Dissolution.” Rad. Waste Manag. Env. Restoration (in press).Google Scholar
2 Aagaard, P. and Helgeson, H.C., Am. J. Sci. 282, 237 (1982).CrossRefGoogle Scholar
3 Grambow, B., in Scientific Basis for Nuclear Waste Management XVII, edited by Van Konynenburg, R. and Barkatt, A. (Mat. Res. Soc. Proc., Pittsburgh, PA, 1994), this issue.Google Scholar
4 Grambow, B., in Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C.M., Stone, J.A., and Ewing, R.C. (Mat. Res. Soc. Proc. 44, Pittsburgh, PA, 1985) pp. 15–27.Google Scholar
5 Pigford, T.H., Chambré, P.L., and Lee, W.W.-L., A Review of Near-Field Mass Transfer in Geologic Disposal Systems, LBL-27045, Lawrence Berkeley Laboratory, Berkeley, CA (1990).CrossRefGoogle Scholar
6 Toride, N., Leij, F.J., and van Genuchten, M.T., Water Resour. Res. 29 (7), 2167–2182 (1993).CrossRefGoogle Scholar
7 Grindrod, P.M., Williams, M., Impey, M., and Grogan, H., STRENG: A Source Term Model for Vitrified High Level Waste, NAGRA Technical Report, NTB 90-48, Badan, Switzerland (1990).Google Scholar
8 Robinson, P. and Worgan, K., Radionuclide Migration Modelling in CALIBRE, SKI TR 89-9, Stockholm, Sweden (1989).Google Scholar
9 McGrail, B.P. and Engel, D.W., in Scientific Basis for Nuclear Waste Management XVI, edited by Interrante, C.G. and Pabalan, R.T. (Mat. Res. Soc. Proc. 294, Pittsburgh, PA, 1993) pp. 215–223.Google Scholar
10 Noorishad, J., Tsang, C.F., Perrochet, P., and Musy, A., Water Resour. Res. 28 (2), 551–561 (1992).CrossRefGoogle Scholar
11 Yeh, G.T. and Tripathi, V.S., Water Resour. Res. 27, 3075–3094 (1991).CrossRefGoogle Scholar